首页> 外国专利> Extraction method for separating uranium, plutonium, and fission products from compositions containing same

Extraction method for separating uranium, plutonium, and fission products from compositions containing same

机译:从含有铀,p和裂变产物的组合物中分离铀,p和裂变产物的提取方法

摘要

834,529. Separation of plutonium. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 11, 1944 [April 3, 1943], No. 4577/44. Class 39(4). Plutonium is separated from an aqueous nitric acid solution of neutron-irradiated uranium, in which the plutonium is in its fluoride-insoluble (plutonous) state, by extraction with an organic solvent which extracts uranyl nitrate, leaving plutonous nitrate and fission products in the aqueous phase. The aqueous phase may then be oxidised and contacted again with the solvent which extracts both plutonium and any remaining uranium, most of the fission products again remaining in the aqueous phase. Agitation of this extract with water containing a reducing agent causes plutonium to pass into the water layer from which it may be precipitated, e.g. as fluoride, iodate, or hydroxide. Alternatively a reducing agent may be added to the solvent extract to precipitate the plutonium. The preferred solvent is diethyl ether, but others referred to are methyl ethyl ether, isopropyl ether, methyl ethyl ketone, nitropropane, nitrobutane, and a mixture of acetone and xylene. Suitable oxidising agents are listed, examples being sodium dichromate and chlorine. The reducing agent may be sulphur dioxide or hydrogen peroxide. To assist the extractions, soluble salts, for example lithium nitrate or aluminium nitrate, may be added to the aqueous solution. The Specification as open to inspection under Sect. 91 describes also the extraction with ether of an initial solution in which the plutonium is in the oxidised state ; both plutonium and uranium pass into the solvent layer which is shaken with water containing sulphur dioxide as a reducing agent to separate plutonium. This subject-matter does not appear in the Specification as accepted.
机译:834,529。 of的分离。联合王国原子能机构。 1944年3月11日[1943年4月3日],编号4577/44。 39(4)类。通过用萃取硝酸硝酸铀酰的有机溶剂萃取,从中子辐照铀的硝酸水溶液中分离出which,其中(处于氟化物不溶(()状态,而在水溶液中留下硝酸lu和裂变产物相。然后可将水相氧化并再次与萃取contact和任何剩余铀的溶剂再次接触,大多数裂变产物仍保留在水相中。用含有还原剂的水搅动该提取物,使to进入水层,在其中可能沉淀出it。如氟化物,碘酸盐或氢氧化物。或者,可以将还原剂添加到溶剂提取物中以沉淀the。优选的溶剂是二乙醚,但其他指的是甲基乙基醚,异丙基醚,甲基乙基酮,硝基丙烷,硝基丁烷以及丙酮和二甲苯的混合物。列出了合适的氧化剂,例子是重铬酸钠和氯。还原剂可以是二氧化硫或过氧化氢。为了辅助提取,可将可溶性盐,例如硝酸锂或硝酸铝添加到水溶液中。该规范可供本节检查。图91还描述了用醚萃取initial处于氧化态的初始溶液; p和铀都进入溶剂层,然后与含有二氧化硫作为还原剂的水一起振摇以分离p。该主题未在接受的规范中出现。

著录项

  • 公开/公告号US2811415A

    专利类型

  • 公开/公告日1957-10-29

    原文格式PDF

  • 申请/专利权人 SEABORG GLENN T;

    申请/专利号US19430481660

  • 发明设计人 SEABORG GLENN T.;

    申请日1943-04-03

  • 分类号C22B60/02;G21C19/46;

  • 国家 US

  • 入库时间 2022-08-23 22:03:15

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